ML20008E367
| ML20008E367 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/26/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Jones OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8010270420 | |
| Download: ML20008E367 (1) | |
Text
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UNITED STATES CENTRAL FILES
,# 80 NUCLEAR REGULATORY COMMISSION PDR:HQ
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NSIC September 26, 1980 STATE Docket No.
50-285 Omaha Public Power District ATTN:
W. C. Jones, Division Manager -
Production Operations 1623 Harney Street Omaha, Nebraska 68102 Gentlemen:
This IE Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee cctions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,7
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(
Karl V. Seyfric Director
Enclosures:
1.
I::: Iaiormation Notice No. 80-34 2.
Recently Issued IE Information Notices cc:
S. C. Stevens, Manager Fort Calhoun Station Post Office Box 98 Fort Calhoun, Nebraska 68102 1
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8010270
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' 9h SSINS No.:
6835 o W' hM Accession No.:
8008220239 IEIN 80-34 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No.80-12 IE Information Notice No.: 80-34 September 26, 1980 Page 1 of 1 BORON DILUTION OF REACTOR COOLANT DURING STEAM GENERATOE DECONTAMINATION Description of Circumstances:
Recently two ins (ances of boron dilution of the reactor coolant system have occurred.
Both cases were a result of high pressure washing of the steam generator tube sheets for decontamination to reduce the radiation levels during eddy current testing and related steam generator work.
On May 29, 1980, Trojan Nuclear Plant miscalculated the excess boric acid required to offset the demineralized water used in washing the tube sheets.
This resulted in the boron concentration of the primary coolant being reduced to less than the minimum required by the Technical Specifications.
The dilu-tion was, however, expected since the wash water was allowed to enter the reactor vessel through the nozzles.
On July 5, 1980, San Onofre Unit 1 inadvertently diluted the reactor coolant boron concentration when the high pressure demineralized flushing waier leaked by a dislodged nozzle seal. -The inflatable seals had been installed to prevent the non-borated water from entering the reactor.
The resulting boron concentra-tion was greater than required for shutdown margin, but the positive reactivity added was in excess of that allowed by the Technical Specifications.
This Information Notice is provided to identify potential problem areas involved with decontaminating specific areas of steam generators.
It is expected that recipients will review the potential hazards involved and consider increased monitoring of 1) inflatable seal performance, 2) vessel level, and 3) boron concentration.
Increasing the boron concentration of the primary system prior to performing any decontamination activities or using borated water for washing should also be considered.
It is expected that recipients will review this information for possible applicability to their facilities.
No specific action or response is requested at this time.
If you have any questions regarding this matter, please contact the' Director of the appropriate Regional Office.
IE Information No. 80-34 September 26, 1980 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject ~
Date Issued To Notice No.
Issued 80-28 Prompt Reporting Of 6/13/80 All applicants for and Required Information holders of nuclear power to NRC reactor construction permits Supp. to Notification of 7/29/80 All holders of Reactor 80-06~
Significant Events at Operating Licenses (OLs)
Operating Power Reactor and to near term Facilities operating license applicants 80-29 Broken Studs on Terry 8/7/80 All light water reacto'r Turbine Steam Inlet facilities holding Flange power reactor Operating License (OL) or Construc-tion Permit (CP) 8 80-30 Potential for Unaccept-8/19/80 All boiling water reactor able Interaction Between facilities holding power the Control Rod Drive Scram reactor Operating Licenses Function and Non-Essential (OLs) or Construction Control Air at Certain GE BWR Permits (cps)
Facilities 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding volt type K-600S and Operating Licenses or and K-DON 600S circuit Construction Permits breakers (cps) 80 Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state li'_nsees sive-use shipments of radioactive materials 80-33 Determination of Tele-9/15/80 All teletherapy therapy Timer Accuracy (G3) licensees Enclosure d
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